ML20079L786
| ML20079L786 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/16/1983 |
| From: | Copeland V COMMONWEALTH EDISON CO., ISHAM, LINCOLN & BEALE |
| To: | Callihan A, Cole R, Smith I Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8302230446 | |
| Download: ML20079L786 (2) | |
Text
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- 7 ISHAM, UNCOLN & BEALE COUNSELORS AT LAW
'83 EB 22 P1 :08 THREE FIRSTNATIONAL PLAZA CHICAGO. ILUNOIS 60602
- _, ; 3; yg t EDwut0 S. ISHAM, 1872-1902 -
'U 5 E9 V CWASHINGTON OFFICE R ERTT UN
, M1889 EL 26 MjCfl 1120 CONNE T AVENU E. N.W.
WASHINGTON. D C. 20036 -
February 16, 1983 Mr. Ivan W. Smith Dr. Richard F. Cole Administrative Judge & Chairman Atomic Safety and Licensing Atomic Safety and Licensin~g Board Panel Board Panel U.S. Nuclear Regulatory Room 428 Commission-East West / West Towers Bldg.
Washington, D.C.
20555 4350 East West Highway Bethesda, MD 20114 Dr. A. Dixon Callihan Union Carbide Corporation P.O. Box Y Oak Ridge, Tennessee 37830 Re:
In The Matter of Commonwealth Edison Company, Byron Station, Units 1 & 2 Docket Nos. 50-454 and 50-455 Gentlemen:
In accordance with the disclosure requirements of the McGuire case,*/ I am enclosing'a letter dated February 15, 1983 from T.R.
Tramm, Nuclear Licensing Administrator for Commonwealth Edison Company, to Harold R.
Denton, Director of the NRC's Office of Nuclear Reactor Regulation.
Mr. Tramm's letter is relevant to DAARE/ SAFE Contention 9a which, as limited by the Atomic Safety and Licensing Board, concerns the poten-tial for a bubble collapse waterhammer in the feedwater bypass line similar to the one that occurred at the KRSKO plant in Yogoslavia.
The purpose of this filing is to apprise the Licensing Board and parties of changes to the Feedwater Bypass System and the Auxiliary Feedwater System.
As more fully explained in Mr. Tramm's letter, these changes are as follows:
1.
Edison plans to install temperature monitoring instrumentation on the feedwater bypass piping near the auxiliary nozzle and to remove the check valve also co-incidentally located in the bypass piping near the auxiliary
- /
Duke Power Company (William B. McGuire Nuclear Station, Units 1 and 2), ALAB-143, 6 AEC, 623, 625 (1973).
B302230446 830216 PDR ADOCK 05000454 O
PDR 0
February 16, 1983 Page Two
. nozzle.
The Licensing Board and.the parties were previously apprised of this action and the reasons therefore in my letter' of February 10, 1983 and the Affidavit of Kanneth Ainger attached thereto.
2.
Edison plans to install a check valve on the.
discharge piping of each auxiliary.feedwater pump.
This addition will provide redundant. backflow protection and minimize the likelihood of backleakage through the auxiliary feedwater system.
Very truly yours, Victor G. Copeland One of the Attorneys for Commonwealth Edison Ccmpany VGC:ldj Enclosure cc:
Service List
Commonwe:ith Edison y %~. "" ' Ons First National Piara. Cheago. Ithnois ri Address R: ply to: Post Offica Box 767 Chicaoo lilinois 60690 February 15, 1983 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station: Units 1 and 2 Waterhammer Prevention NRC Docket Nos. 50-454/455 and 50-456/457 References (a):
September 9, 1982 letter from T. R.
Tramm to H.
R. Danton (b):
February 10, 1983 letter from V.
G.
Copeland to'the Byron ASLB
Dear Mr. Denton:
This is to provide information regarding the prevention of steam generator waterhammer at Byron and Braidwood stations.
This supplements the information which was provided to the NRC in reference (a).
In reference (a), we indicated that constant feedwater flow through the upper steam generator nozzles would preclude the need for temperature monitoring.of this piping.
We then believed that waterhammer could effectively be prevented without installation of that additional instrumentation.
Recently, we have identified certain circumstances during plant startup and shutdown in which continuous feedwater addition is impractical.
Therefore,' temperature monitoring instrumentation will be installed on the feedwater bypass piping close to the auxiliary nozzle.
This will alert the operator to potential waterhammer situations so that feedwater flow can be reinitiated without inducing waterhammer.
This has been discussed in the affidavit of.
Kenneth A. Ainger which was attached to reference (b).
Mr. Ainger's affidavit also noted that check valves in the auxiliary nozzle piping were being removed to assure the effective-ness of controlled-closure check valves farther upstream.
A typical diagram of this piping was provided in Figure 6 attached to reference (a).
The check valves being removed are the ones closest to the steam generators, identified in the typical diagram (Figure 6) as valve FWO37A.
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R. Denton February 15, 1983
-Removal of these check valves necessitates-the addition of other check valves to provide redundant back flow protection in certain piping.
Without additional check valves in the auxiliary feedwater pump discharge piping, there is only one check valve in the piping connecting the upper steam generator' nozzles and thez
- condensate storage tank via the auxiliary'feedwater pump _miniflow lines.
An additional check valve will'therefore be installed in.the discharge piping of each auxiliary 'feedwater pump to minimize back-leakage through this path.
A revised version of Figure. 6 is attached
_ to document the-location of these'new valves.
Please address further questions ~regarding this matter to
_this office.
One signed original and fifteen copies of this letter and the attached figure are provided for your review.
Very truly yours, ft /
rTL6 T. R.
Tramm Nuclear Licensing Administrator im Attachment 6002N
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